Final results concerning the ENEA-Bologna BUGJEFF311.BOLIB working cross section library validation on the Iron-88 single material (iron) integral neutron shielding benchmark experiment are presented. The BUGJEFF311.BOLIB library is specifically dedicated to LWR shielding and pressure vessel dosimetry applications. It is a broad-group coupled (47 n + 20 ) working library in FIDO-ANISN format, based on the OECD-NEADB JEFF-3.1.1 evaluated nuclear data library and with the same group structure as the ORNL BUGLE-96 similar library. The analysis of the Iron-88 Winfrith benchmark experiment was performed through 3D transport calculations in Cartesian geometry using the ORNL TORT-3.2 discrete ordinates (SN) code together with the BUGJEFF311.BOLIB library and the BUGLE-96 library as term of comparison. The activation cross sections for the Au-198(n,γ)Au-198 dosimeters and the threshold activation cross sections for the Rh-103(n,n')Rh-103m, In-115(n,n')In-115m, S-32(n,p)P-32 and Al-27(n,α)Na-24 dosimeters were derived from the IAEA IRDF-2002 reactor dosimetry file.
Final Results of the BUGJEFF311.BOLIB Library Validation on the Iron-88 (Fe) Neutron Shielding Benchmark Experiment
Orsi, Roberto;Pescarini, Massimo
2017-11-08
Abstract
Final results concerning the ENEA-Bologna BUGJEFF311.BOLIB working cross section library validation on the Iron-88 single material (iron) integral neutron shielding benchmark experiment are presented. The BUGJEFF311.BOLIB library is specifically dedicated to LWR shielding and pressure vessel dosimetry applications. It is a broad-group coupled (47 n + 20 ) working library in FIDO-ANISN format, based on the OECD-NEADB JEFF-3.1.1 evaluated nuclear data library and with the same group structure as the ORNL BUGLE-96 similar library. The analysis of the Iron-88 Winfrith benchmark experiment was performed through 3D transport calculations in Cartesian geometry using the ORNL TORT-3.2 discrete ordinates (SN) code together with the BUGJEFF311.BOLIB library and the BUGLE-96 library as term of comparison. The activation cross sections for the Au-198(n,γ)Au-198 dosimeters and the threshold activation cross sections for the Rh-103(n,n')Rh-103m, In-115(n,n')In-115m, S-32(n,p)P-32 and Al-27(n,α)Na-24 dosimeters were derived from the IAEA IRDF-2002 reactor dosimetry file.File | Dimensione | Formato | |
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